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DE69008759D1 - Steam generator for reactors cooled with liquid sodium. - Google Patents

Steam generator for reactors cooled with liquid sodium.

Info

Publication number
DE69008759D1
DE69008759D1 DE69008759T DE69008759T DE69008759D1 DE 69008759 D1 DE69008759 D1 DE 69008759D1 DE 69008759 T DE69008759 T DE 69008759T DE 69008759 T DE69008759 T DE 69008759T DE 69008759 D1 DE69008759 D1 DE 69008759D1
Authority
DE
Germany
Prior art keywords
steam generator
liquid sodium
reactors cooled
reactors
cooled
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Expired - Fee Related
Application number
DE69008759T
Other languages
German (de)
Other versions
DE69008759T2 (en
Inventor
Charles Edward Boardman
John Paul Maurer
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
General Electric Co
Original Assignee
General Electric Co
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by General Electric Co filed Critical General Electric Co
Application granted granted Critical
Publication of DE69008759D1 publication Critical patent/DE69008759D1/en
Publication of DE69008759T2 publication Critical patent/DE69008759T2/en
Anticipated expiration legal-status Critical
Expired - Fee Related legal-status Critical Current

Links

Classifications

    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22—STEAM GENERATION
    • F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
    • F22B1/00—Methods of steam generation characterised by form of heating method
    • F22B1/02—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers
    • F22B1/06—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers the heat carrier being molten; Use of molten metal, e.g. zinc, as heat transfer medium
    • F22B1/063—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers the heat carrier being molten; Use of molten metal, e.g. zinc, as heat transfer medium for metal cooled nuclear reactors
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactor types
    • G21C1/02—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders
    • G21C1/03—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders cooled by a coolant not essentially pressurised, e.g. pool-type reactors
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Landscapes

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • High Energy & Nuclear Physics (AREA)
  • General Engineering & Computer Science (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Sustainable Development (AREA)
  • Sustainable Energy (AREA)
  • Thermal Sciences (AREA)
  • Mechanical Engineering (AREA)
  • Plasma & Fusion (AREA)
  • Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
DE69008759T 1989-03-13 1990-03-08 Steam generator for reactors cooled with liquid sodium. Expired - Fee Related DE69008759T2 (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US07/322,481 US4983353A (en) 1989-03-13 1989-03-13 Novel passive approach to protecting the primary containment barrier formed by the intermediate heat exchanger from the effects of an uncontrolled sodium water reaction

Publications (2)

Publication Number Publication Date
DE69008759D1 true DE69008759D1 (en) 1994-06-16
DE69008759T2 DE69008759T2 (en) 1994-12-08

Family

ID=23255093

Family Applications (1)

Application Number Title Priority Date Filing Date
DE69008759T Expired - Fee Related DE69008759T2 (en) 1989-03-13 1990-03-08 Steam generator for reactors cooled with liquid sodium.

Country Status (4)

Country Link
US (1) US4983353A (en)
EP (1) EP0388083B1 (en)
JP (1) JPH02272201A (en)
DE (1) DE69008759T2 (en)

Families Citing this family (14)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2664773B2 (en) * 1989-05-23 1997-10-22 株式会社東芝 Liquid metal cooled reactor cooling system
JPH04140693A (en) * 1990-09-29 1992-05-14 Toshiba Corp Tank type nuclear reactor
US9275760B2 (en) * 2009-09-25 2016-03-01 Terrapower, Llc Heat exchanger, methods therefor and a nuclear fission reactor system
US20110075787A1 (en) 2009-09-25 2011-03-31 Searete Llc, A Limited Liability Corporation Of The State Of Delaware Heat exchanger, methods therefor and a nuclear fission reactor system
WO2011078871A2 (en) * 2009-09-25 2011-06-30 Searete, Llc A heat exchanger, methods therefor and a nuclear fission reactor system
US20110075786A1 (en) * 2009-09-25 2011-03-31 Searete Llc, A Limited Liability Corporation Of The State Of Delaware Heat exchanger, methods therefor and a nuclear fission reactor system
JP2011075490A (en) * 2009-10-01 2011-04-14 Toshiba Corp Liquid metal-cooled nuclear reactor
CN102563590B (en) * 2010-12-22 2014-04-02 清华大学 Saturated steam generator
CN102927837A (en) * 2012-11-02 2013-02-13 镇海石化建安工程有限公司 Heat exchanger structure
US9773574B2 (en) * 2013-11-04 2017-09-26 The Regents Of The University Of California Systems and methods for enhancing isolation of high-temperature reactor containments
CN207038180U (en) * 2016-08-03 2018-02-23 泰拉能源有限责任公司 Nuclear energy production facility
CN107270269A (en) * 2017-05-05 2017-10-20 中广核研究院有限公司 Multiple-unit pipe type steam generator
CN107393602B (en) * 2017-07-31 2019-08-02 江苏华洋新思路能源装备股份有限公司 A kind of passive fire resisting relief panel in nuclear power unit fuel treatment region
CN110732295B (en) * 2019-11-15 2024-09-06 中国原子能科学研究院 Steam supply system

Family Cites Families (12)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2074732B1 (en) * 1970-01-22 1974-02-01 Babcock Atlantique Sa
FR2112007A1 (en) * 1970-04-03 1972-06-16 Edf Tube bundle heat exchanger - has internal reservoir to contain overflow surges due to leaks
US3848572A (en) * 1971-08-09 1974-11-19 Westinghouse Electric Corp Steam generator
US3924675A (en) * 1973-05-03 1975-12-09 Us Energy Energy absorber for sodium-heated heat exchanger
JPS5172802A (en) * 1974-12-20 1976-06-24 Hitachi Ltd NETSUKOKANKI
FR2321750A1 (en) * 1975-08-22 1977-03-18 Commissariat Energie Atomique IMPROVEMENT OF THE SECONDARY CIRCUITS OF A NUCLEAR REACTOR
US4163470A (en) * 1977-06-30 1979-08-07 The Babcock & Wilcox Company Industrial technique
FR2509841B1 (en) * 1981-07-17 1986-07-18 Creusot Loire IMPROVEMENT ON SODIUM-WATER STEAM GENERATORS
FR2523268A1 (en) * 1982-03-11 1983-09-16 Novatome DEVICE FOR PRODUCING STEAM BY EXCHANGING HEAT BETWEEN A LIQUID-COOLED METAL AND FOOD WATER COMPRISING SEVERAL INTERFACES METAL LIQUID-NEUTRAL GAS
FR2533355B1 (en) * 1982-09-22 1988-07-08 Commissariat Energie Atomique SECONDARY HEATER CIRCUIT FOR A NUCLEAR REACTOR COOLED BY A LIQUID METAL AND STEAM GENERATOR SUITABLE FOR SUCH A CIRCUIT
FR2544053B1 (en) * 1983-04-07 1985-06-28 Commissariat Energie Atomique STEAM GENERATOR FOR A LIQUID METAL COOLED REACTOR
US4905757A (en) * 1987-11-06 1990-03-06 General Electric Company Compact intermediate heat transport system for sodium cooled reactor

Also Published As

Publication number Publication date
JPH02272201A (en) 1990-11-07
DE69008759T2 (en) 1994-12-08
EP0388083B1 (en) 1994-05-11
EP0388083A1 (en) 1990-09-19
US4983353A (en) 1991-01-08

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Legal Events

Date Code Title Description
8364 No opposition during term of opposition
8339 Ceased/non-payment of the annual fee